Rchr
J-GLOBAL ID：202101015031094144
Update date: Mar. 31, 2024
Toyota Kodai
トヨタ コウダイ | Toyota Kodai
Affiliation and department：
Research field (2)：
Nuclear engineering
, Structural and functional materials
Research theme for competitive and other funds (1)：
- 2021 - 2025 Development of multi-type simultaneous measurement method in radiation field toward the creation of innovative materials
Papers (6)：
-
Toyota Kodai, Imagawa Yuya, Onizawa Takashi, Kato Shoichi, Furuya Yoshiyuki*. Validation of the applicability of the best-fit fatigue curves for 550$^{\circ}$C in Mod.9Cr-1Mo steel to 1$\times$10$^{11}$ cycles. Nihon Kikai Gakkai Rombunshu (Internet). 2023. 89. 928. 23-00206\_1-23-00206\_15
-
Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka, et al. Sodium-cooled Fast Reactors. Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3. 2022. 631
-
Toyota Kodai, Onizawa Takashi, Wakai Takashi, Hashidate Ryuta, Kato Shoichi. Material data acquisition activities to develop the material strength standard for sodium-cooled fast reactors. Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet). 2022. 10
-
Ando Masanori, Toyota Kodai, Hashidate Ryuta, Onizawa Takashi. Evaluation of the Japanese fatigue test data in Gr.91 for elevated temperature design. Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet). 2021. 10
-
Toyota Kodai, Hashidate Ryuta, Takahashi Keita, Yada Hiroki, Takaya Shigeru. Proposal of maintenance rationalization for next-generation fast reactors based on the analysis of the prolonged maintenance of the prototype fast-breeder reactor in Japan, "Monju", 2; Analysis of maintenance plan of "Monju" in reactor cold shutdown. Hozengaku. 2021. 20. 2. 95-103
ｍore...
MISC (1)：
-
Imagawa Yuya, Toyota Kodai, Onizawa Takashi, Kato Shoichi. FBR metallic materials test manual (2023 revised edition). JAEA-Testing 2023-004. 2024. 76
Lectures and oral presentations (13)：
-
Development of fatigue testing techniques using solid round bar miniature specimens
(日本金属学会2024年春期(第174回)講演大会)
-
Thermal aging effects on high temperature tensile properties of Mod.9Cr-1Mo steel
(日本金属学会2024年春期(第174回)講演大会)
-
Development of the material strength standard of 316FR steel and modified 9Cr-1Mo steel for next-generation fast reactor in Japan
(27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27))
-
Characterization of iron-based and tungsten-based high-entropy alloys
(Nuclear Materials Conference 2022 (NuMat 2022))
-
Machine learning of ultrasonic phased-array images for flaw detection
(日本機械学会第26回動力・エネルギー技術シンポジウム)
ｍore...
Return to Previous Page
